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A history of major Hanford facilities and processes involving radioactive material. [Contains glossary]

Description: The Hanford Environmental Dose Reconstruction (HEDR) Project was established in 1987 to estimate radiation doses that people could have received from nuclear operations at the Hanford Site since 1944. Hanford Site operations began in 1944 to produce plutonium for nuclear weapons. This effort included fabricating fuel elements, irradiating the fuel in nuclear reactors, and separating the resulting plutonium from uranium and fission byproducts. To build a foundation for the first step in estimati… more
Date: March 1, 1991
Creator: Ballinger, M.Y. & Hall, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission product iodine during early Hanford-Site operations: Its production and behavior during fuel processing, off-gas treatment and release to the atmosphere

Description: The Hanford Environmental Dose Reconstruction (HEDR) Project was established to estimate the radiological dose impact that Hanford Site operations may have made on the local and regional population. This impact is estimated by examining operations involving radioactive materials that were conducted at the Hanford Site from the startup of the first reactor in 1944 to the present. HEDR Project work is divided among several technical tasks. One of these tasks, Source Terms, is designed to develop … more
Date: May 1, 1991
Creator: Burger, L.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of concentration mechanisms for organic wastes in underground storage tanks at Hanford

Description: Pacific Northwest Laboratory (PNL) has conducted an initial conservative evaluation of physical and chemical processes that could lead to significant localized concentrations of organic waste constituents in the Hanford underground storage tanks (USTs). This evaluation was part of ongoing studies at Hanford to assess potential safety risks associated with USTs containing organics. Organics in the tanks could pose a potential problem if localized concentrations are high enough to propagate combu… more
Date: September 1, 1992
Creator: Gerber, M. A.; Burger, L. L.; Nelson, D. A.; Ryan, J. L. (Pacific Northwest Lab., Richland, WA (United States)) & Zollars, R. L. (Washington State Univ., Pullman, WA (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium by pyroredox processing

Description: Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in impure scrap with less than 95% plutonium. This plutonium metal was further purified by pyrochemical electrorefining. During development of the procedures, depleted electrorefining anodes were processed, and over 80% of the plutonium was recovered as high-purity metal in one electrorefining cycle. Over 40 kg of plutonium has been recovered from 55 kg of impure anodes with our procedures. 6 refs.,… more
Date: September 1, 1985
Creator: McNeese, J.A.; Bowersox, D.F. & Christensen, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Items for over-all Redox contamination improvement

Description: In view of contamination difficulties within the Redox operation, number of items are being considered to improve this situation. It is the objective of this document to list and describe seven times which it is felt would contribute most toward improvement. It is also an objective to present for RDS-D-12 Group consideration the recommendations of representatives from Manufacturing, Technical, and Design in these matters with the expectation that a project proposal written in general terms for … more
Date: January 13, 1955
Creator: Rohrmann, C. A.; Wilson, B. D. & Merrill, E. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Redox contamination: Terminal status report

Description: The Redox ruthenium contamination problem has two distinct phases; the environs contamination as a result of stack emissions, and the in-canyon contamination which controls time and cost factors for plant maintenance. On stack emissions, the probability of serious environs contamination exists so long as the batch-type, permanganate headend ruthenium volatilization process is used. Knowledge of the characteristics of volatilized ruthenium is not adequate today to give complete assurance that th… more
Date: July 13, 1954
Creator: Anderson, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed alternate dissolving flowsheets for the Redox plant

Description: Current operation of the Redox plant dissolvers results in evolution of ammonia during the slug jacket removal step. Staggering the schedules of the dissolving cycles of the three dissolvers is being practiced at present to prevent the formation of ammonium nitrate crystals in the stack gases, but this procedure limits the dissolver capacity. Steps are being taken to provide ammonia scrubbers for the dissolvers to eliminate this need for close scheduling of dissolving operations. It has been pr… more
Date: August 13, 1954
Creator: Curtis, M. H. & Harmon, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control of DWPF melter feed composition

Description: The Defense Waste Processing Facility will be used to immobilize Savannah River Site high-level waste into a stable borosilicate glass for disposal in a geologic repository. Proper control of the melter feed composition in this facility is essential to the production of glass which meets product durability constraints dictated by repository regulations and facility processing constraints dictated by melter design. A technique has been developed which utilizes glass property models to determine … more
Date: December 31, 1989
Creator: Brown, K. G.; Edwards, R. E.; Postles, R. L. & Randall, C. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fixation of Hanford sludge by conversion to glass

Description: Redox and Purex process sludges stored at Hanford can be converted to durable borosilicate glasses by melting at 1100--1400/sup 0/C charges containing 30 to 40 weight percent washed, dried sludge, 45 to 60 weight percent SiO/sub 2/, 5 to 15 weight percent B/sub 2/O/sub 3/, 0 to 10 weight percent Na/sub 2/O, 0 to 5 weight percent Li/sub 2/O, and 0 to 5 weight percent TiO/sub 2/. Leach rates in deionized water (25/sup 0/C) for the glasses range from about 10/sup -7/ to 10/sup -5/ g/cm/sup 2/-day.
Date: March 1, 1977
Creator: Kupfer, M. J. & Schulz, W. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization and Leach Testing for PUREX Cladding Waste Sludge (Group 3) and REDOX Cladding Waste Sludge (Group 4) Actual Waste Sample Composites

Description: A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan.(a) The testing program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Eight broad waste groupings were def… more
Date: February 13, 2009
Creator: Snow, Lanee A.; Buck, Edgar C.; Casella, Amanda J.; Crum, Jarrod V.; Daniel, Richard C.; Draper, Kathryn E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization and Leach Testing for REDOX Sludge and S-Saltcake Actual Waste Sample Composites

Description: This report describes processing and analysis results of boehmite waste type (Group 5) and insoluble high Cr waste type (Group 6). The sample selection, compositing, subdivision, physical and chemical characterization are described. Extensive batch leach testing was conducted to define kinetics and leach factors of selected analytes as functions of NaOH concentration and temperature. Testing supports issue M-12 resolution for the Waste Treatment Plant.
Date: July 10, 2008
Creator: Fiskum, Sandra K.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Hubler, Timothy L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of uranium and plutonium from Redox off-standard aqueous waste streams

Description: In the operation of countercurrent extraction columns as in the Redox process, it is possible, and probable, that from unexpected behaviour of a column, operator error, colloid formation, etc., there will result from time to time excessive losses of uranium and plutonium in the overall process. These losses will naturally accumulate in the waste streams, particularly in the aqueous waste streams. If the loss is excessively high, and such lost material can be recovered by some additional method,… more
Date: December 31, 1949
Creator: Holm, C. H. & Matheson, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RDA No. DC-7 -- Capacity basis for increasing production from Redox -- 202-S

Description: The outstanding economy of the Redox process when compared with the BiPO{sub 4} process dictates that as much production as possible, and as soon as possible, should be shifted from the BiPO{sub 4} process to Redox (202-S). It is proposed that the capacity basis for the subject study be for as much as 200 tons of uranium and up to 105 kilograms of plutonium per month, assuming that facilities proposed for these capacity levels will not interfere with the operating flexibility of the plant, if i… more
Date: November 8, 1951
Creator: Rohrmann, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly report, January 1951--March 1951, Chemical Research Section

Description: The current Relox flowsheet proposes precipitation of plutonium peroxide from IIBP solution concentrated by evaporation to 10 g Pu/1 and ca. 5.5 M HNO{sub 3}. Such a solution might have an Al{sup +++} concentration as high as 0.02 M with stainless steel corrosion product concentrations of the order of magnitude of those found in AT solution diluted to 10 g Pu/l. Methods for the precipitation of plutonium peroxide from this type of solution, either with or without partial neutralization of the n… more
Date: April 16, 1951
Creator: Hill, O. F. & Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Exceeding always-safe ratio in F-2 and F-1 tanks: Number 2, CY-63

Description: The always critically-safe ratio of plutonium to enriched uranium was exceeded in the F-2 and V-1 vessels on June 6, 1963. The allowable always-safe ratio at the time of the incident vas 627 grams per ton. The actual ratio achieved vas 673 grams per ton. This report details the investigation into events leading to the over-batch.
Date: October 7, 1963
Creator: Malody, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Events of importance for week ending January 26, 1949

Description: Redox operations and waste metal recovery are reported. Construction in the 100-H, 100-DR, P-10 area pile areas and in the 234-5, 241-BY waste storage, and redox areas, process areas and Richland village are described. Visitor information is given. And construction progress at Schenectady is reported.
Date: January 28, 1949
Creator: Schlemmer, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Events of importance for week ending August 3, 1949

Description: The redox and pile operations are reported on. Construction in 100 (Pile), 200 (Separation), and 300 (Metal Fabrication) areas is described. General work in the Richland commercial areas and on the Southern Railroad connection is also described. Personnel information is disclosed.
Date: August 5, 1949
Creator: Schlemmer, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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